Clarification of NRC Requirements for Emergency Response Facilities at Each Site (Generic Letter 80-34)

GL80034
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D.C. 20555
April 25, 1980
ALL POWER REACTOR LICENSEES
Gentlemen:
SUBJECT: CLARIFICATION OF NRC REQUIREMENTS FOR EMERGENCY RESPONSE
FACILITIES AT EACH SITE
Over the past several months the NRC staff has been conducting reviews of
each licensee's proposal to upgrade their plant to cope with emergencies.
The lessons learned and emergency planning review teams have identified
areas where clarification of the NRC position is necessary. Our previous
requirements for the TSC have been modified to allow an onsite TSC in close
proximity to the control room that would not meet the habitability
requirements, provided that a backup, habitable TSC is located near the
site.
It is the purpose of this letter to set forth clarification of NRR's
requirements for the three emergency response facilities defined in my
September 13, 1979 letter to "All Operating Nuclear Power Plants".
Additional specific criteria for these facilities is under development. The
schedule for implementing these requirements has not changed.
If you have, any questions regarding this clarification, please contact the
NRC Project Manager for your facility.
Sincerely,
Darrell G. Eisenhut, Acting Director
Division of Reactors
Office of Nuclear Reactor Regulation
Enclosure:
Emergency Response
Facilities
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EMERGENCY RESPONSE FACILITIES
Onsite Technical Support Center
An onsite technical support center (TSC) shall be maintained by each
operating nuclear power plant. The TSC shall be separate from, but in very
close proximity to, the control room and be within the plant security
boundary. While care must be taken in selecting technical input available in
the TSC, it appears likely that access to additional control room data would
be required during an emergency. The location of the TSC shall also be such
as to facilitate occasional face-to-face contact between key control room
and TSC supervisors (management presence). The emphasis in designing the TSC
information displays should be on reactor systems status. Those individuals
who are knowledgeable of and responsible for engineering and management
support of reactor operations in the event of an accident will report to the
TSC (minimum size 25 persons including 5 NRC). Those persons who are
responsible for the overall management of the utility resources including
recovery following an accident (e.g., corporate mangers) should report to
the EOF (see below). Upon activation, the TSC will provide the main
communication link between the plant and the operator's near-site Emergency
Operations Facility, and the main communication link to the NRC for plant
operations matters. The TSC must be habitable because of site-specific
considerations, a backup TSC which does meet the habitability requirements
must be provided on or near the site. Parameters transmitted by any nuclear
data link installed to meet future NRC requirements should be available for
display in the TSC and the EOF.
Onsite Operational Support Center (Assembly Area)
The Operational Support Center shall be the place to which the operations
support personnel report in an emergency situation. Communications will be
provided with the control room, OTSC and EOF.
Emergency Operations Facility (Near-Site)
The Emergency Operations Facility (EOF) will be operated by the licensee for
continued evaluation and coordination of licensee activities related to an
emergency having or potentially having environmental consequences. The EOF
must have the capability to display the same plant data and radiological
information as will be required for transmittal to the NRC. The EOF will
have sufficient space to accommodate representatives from Federal, State and
local governments if desired by those agencies, including facilities for the
senior NRC representative (10) on-site. In addition, the major State and
local response agencies may perform data analysis jointly with the licensee.
Overall management of utility resources including recovery operations
following an accident (e.g., by corporate management) shall be managed from
this facility. Press facilities for about 20 people shall be available at
the Emergency Operation Facility (periodic use). Site meteorology should be
used to the extend practical for determining the EOF location. THe EOF
should be located within about one mile of the reactor. The EOF should be a
substantial structure, providing significant shielding factors from direct
radiation and the capability to isolate ventilation systems. Filtration
systems (at least HEPA filters) shall be provided in new structures.
Arrangements shall be made to activate an alternate EOF in the event that
the nearsite EOF becomes uninhabitable.
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PLANTS UNDER OL REVIEW
1. Farley 2 50-364
2. Byron 1/2 50-454, 455
3. Braidwood 1/2 50-456/457
4. LaSalle 1/2 50-373,374
5. Midland 1/2 50-329, 330
6. McGuire 50-369, 370
7. So. Texas 1/2 50-498, 499
8. Shoreham 50-322
9. Waterford 50-382
10. Grand Gulf 1/2 50-416/417
11. Diablo Canyon 1/2 50-275, 323
12. Susquehana 1/2 50-387,388
13. Salem 2 50-311
14. Summer 1 50-395
15. San Onofre 2/3 50-361, 362
16. Bellefonte 1/2 50-438, 439
17. Watts Bar 1/2 50-390, 391
18. Sequoyah 1/2 50-327, 328
19. Comanche Peak 1/2 50-445, 446
20. North Anna 2 50-339
21. WPPSS-2 50-397
22. Fermi 2 50-341
23. Zimmer 1 50-358